ML17332A827
| ML17332A827 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/30/1995 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17332A828 | List: |
| References | |
| AEP:NRC:1124C, GL-90-02, GL-90-2, NUDOCS 9507070175 | |
| Download: ML17332A827 (6) | |
Text
PRIORITY (ACCELERATED RZDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9507070175 DOC.DATE: 95/06/30 NOTARIZED: YES DOCKET N
FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 P
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana
& Michigan Ele R
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58 DPR-74,changing'S Section 5.3.1 to allow fuel reconstitution,per GL 90-02, 0
Suppl 1.
DISTRIBUTION CODE:
A014D COPIES RECEIVED:LTR ENCL SIZE:
R TITLE: Generic Ltr 90-02 re Line-Item Tech Spec Improvement Alternative Re I
NOTES:
RECIPIENT ID CODE/NAME PD3-1 PD HICKMAN J INTERNAL NSEtR e.
/DSSA/SRXB RES/DS IR/EIB EXTERNAL NOAC COPXES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD11-3 NRR/DSSA
'GC/HDS2 NRC PDR COPXES LTTR ENCL 1
1 1
1 1
0 1
1 D
0 N
NOTE TO ALL s'RZDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL
- DESK, ROOM OWFN SD8 (415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF. COPIES REQUIRED:
LTTR 10 ENCL 9
indiana Michigan Power Company P.O. Box 16631, Columbus, OH 43216 1
June 30, 1995 AEP'NRC'1124C Docket Nos.:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C.
20555 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO ALLOW FUEL RECONSTITUTION (GENERIC LETTER 90-02 SUPPLEMENT 1)
REQUEST FOR ADDITIONALINFORMATION This letter is in response to the changes to submittal AEP:NRC:1124B discussed on June 20, 1995.
As agreed
- upon, the following statement has been incorporated into the wording for the proposed change to technical specification (T/S) Section 5.3.1.
"Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases.
A limited number of lead test assembli'es that have not completed representative testing may be placed in non-limiting core regions."
The attachment contains the revised page for each unit.
These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed at the next regular meeting of the Nuclear Safety and Design Review Committee.
C:~OO79 9507070175
'750630 PDR ADOCK 05000315 PDR pl
C' a
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:1124C In compliance with the requirements of 10 CFR 50.91(b)(1),
copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department of Public Health.
Sincerely, 8F E.
E. Fitz rick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~i4 DAY OF i~ra 1995 No ary Public My Commission Expires:
C~ d'-
5'$'h Attachment CC:
A. A. Blind G. Charnoff J.
B. Martin NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
I'
'I r
ATTACHMENT TO AEP:NRC: 1124C PROPOSED REVISED TECHNICAL SPECIFICATION PAGES